JAFP-15-0103, Core Operating Limits Report, Revision 29 (Cycle 22)
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| Site: | FitzPatrick  |
| Issue date: | 08/18/2015 |
| From: | Defillippo S Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
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Text
JAFP-15-0103 ENCLOSURE 2 Core Operating Limits Report Revision 29 (Non-proprietary Version)
(26 Pages Including Contents)
JAFP-15-0103 Enclosure 2 Contents Core Operating Limits Report 25 Pages
ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR PO\v'ER PL\NT REPORT CORE OPERATING LIMITS REPORT REVISION 29 APPROVED BY:
APPROVED BY:
GENERAL !YL-\NAGER- PLANT OPERATIONS D.
Information Notice This is a non-proprietary version of the James A. FitzPatrick COLR Revision 29, which has proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed bracket as shown here (( )).
CORE OPERATING LIMITS REPORT CYCLE 22 REVISION RECORD Revision Cycle Date Description COLR Rev. 29 is valid for Cycle 22 operation with the impacts of the 29 22 July 2015 elevated 38-39 FSC on bundle flow and core bypass flow addressed in the installed 3D-Monicore databank.
Summary of Changes Rev. 29 Effective upon final approval Applicable for use during Cycle 22 Operation. Revision issued to address the SRLR-Rev.1 (Ref. 3.8) analyses that evaluated the impacts of the Cycle 22 elevated 38-39 FSC on bundle flow and core bypass flow when the installed 3D-Monicore databank contains the implementation of 38-39 FSC adjusted inlet orifice loss coefficients and increased bypass flow for 3DM core monitoring.model.
Update for a SRLR-Rev.1 (Ref. 3.8) reference and for an addition of the specific OLMCPR limits required for cell 38-39 GNF2 fuel.
GESTAR reference updated to the latest revision 21 (Ref. 3.7).
GESTAR Rev. 21 includes the NRC approved use of the analysis code TRACG04 for use in Option I-D stability analyses. COLR reference pointing to the latest revision of GESTAR addresses the concern raised in CR-HQN-2015-00639.
The Fuel Impact report, reference 3.21 is added. It clearly delineates that the SRLR Rev.1 specific OLMCPR limits are only applicable once the 3DMonicore databank for explicit 38-39 FSC model is installed.
This revision record and summary added.
Rev. 28 10/01/2014 Applicable for use during Cycle 22 Operation. Revision issued to update this document for FitzPatrick Reload 21 Cycle 22 cycle dependent data.
GESTAR reference updated to the latest revision 20 (Ref. 3.7).
Update to cycle specific references.
Update for a reference with a latest revision for GNF2 GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)
Update for a reference with the final regulatory approval for PRIME implementation in downstream analysis codes.
FWTR is permitted in Cycle 22 operation.Content of TABLE 8.4 defining MCPR Operating Limit for Final Feedwater Temperature Reduction is added.
This revision record and summary added.
Rev. No. 29 Page 2 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ............................................................................................................................................. 4 2.0 APPLICABILITY................................................................................................................................. 4
3.0 REFERENCES
..................................................................................................................................... 4 4.0 DEFINITIONS .................................................................................................................................... 5 5.0 RESPONSIBILITIES .......................................................................................................................... 6 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS ........................................................................ 6 7.0 PROCEDURE ...................................................................................................................................... 7 7.1 Operating Limit MCPR ........................................................................................................................ 7 7.2 Average Planar Linear Heat Generation Rate (APLHGR) ............................................................ 9 7.3 Linear Heat Generation Rate (LHGR) ............................................................................................ 10 7.4 APRM Allowable Values (Digital Flow Cards) .............................................................................. 11 7.5 RBM Upscale Rod Block Allowable Value ..................................................................................... 12 7.6 Stability Option 1-D Exclusion Region and Buffer Zone. ........................................................... 12 8.0 TABLES AND FIGURES ................................................................................................................ 12 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure .................... 13 TABLE 8.2 MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service .................... 14 TABLE 8.3 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service ...................................................................................................................................... 15 TABLE 8.4 MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction............................................................................................................................ 16 TABLE 8.5 Exposure Dependent APLHGR Limits ............................................................................. 17 TABLE 8.6 Maximum LHGR ................................................................................................................... 18 Figure 8.1 MCPR(F) Factor ................................................................................................................... 19 Figure 8.2 K(P), OLMCPR(P) Factor .................................................................................................. 20 Figure 8.3 Flow-Dependent LHGR Multiplier, LHGRFAC(F) ...................................................... 21 Figure 8.4 Power-Dependent LHGR Multiplier, LHGRFAC(P) .................................................... 22 Figure 8.5 Stability Option 1-D Exclusion Region ............................................................................ 23 Figure 8.6 Cycle 22 Loading Pattern by Bundle Design with the improperly seated FSC Cell 38-39 GNF2 Fuel Types marked ....................................................................................... 24 9.0 USERS GUIDE .................................................................................................................................. 25 Rev. No. 29 Page 3 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 22 of the James A.
FitzPatrick Nuclear Power Plant. The following limits are addressed:
Operating Limit Minimum Critical Power Ratio (MCPR)
Flow Dependent MCPR Limits Average Planar Linear Heat Generation Rate (APLHGR)
Linear Heat Generation Rate (LHGR)
Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)
Allowable Values Stability Option ID Exclusion Region 2.0 APPLICABILITY The plant shall be operated within the limits specified in this report. If any of these limits are exceeded, the corrective actions specified in the Technical Specifications shall be taken.
3.0 REFERENCES
3.1 EN-LI-113, Licensing Basis Document Change process 3.2 JAFNPP Technical Specifications 3.3 EC45913, Cycle 22 Core Reload 3.4 EN-DC-503, 3D Monicore New Cycle Update and Databank Maintenance.
3.5 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.
3.6 GE Report, J.A. FitzPatrick Nuclear Power Plant APRM/RBM/Technical Specifications/Maximum Extended Operating Domain (ARTS/MEOD), NEDC-33087P, Revision 1, September 2005 3.7 General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-21, May 2015; and the U.S. Supplement, NEDE-24011-P-A-21-US, May 2015.
3.8 GNF Report, Supplemental Reload Licensing Report for FitzPatrick Reload 21 Cycle 22, 001N8543-SRLR, Revision 1, July 2015. [EC 58732, ECH-NE-14-00034 R1]
3.9 GNF2 Fuel Design Cycle-Independent Analyses for Entergy FitzPatrick, GE Report, GEH-0000-0074-2662-R1, June 2010. [EC23634, JAF-RPT-08-00013 R1]
3.10 Licensing Topical Report, ODYSY Application for Stability Licensing Calculations Including Option I-D and II Long Term Solutions, NEDE-33213P-A, April 2009 Rev. No. 29 Page 4 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 3.11 GE Letter, R. Kingston to P. Lemberg, Scram Time versus Notch Positions for Option B, REK-E:
02-009, May 28, 2002 3.12 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.
3.13 JD-02-122, Final Feedwater Temperature Reduction Implementation.
3.14 KGO-ENO-JB1-13-085, NEDC-33270P, R5, GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), May 2013 3.15 GNF Report, Fuel Bundle Information Report for FitzPatrick Reload 21 Cycle 22, 001N8544-FBIR, Revision 0, Class II, August 2014. [EC 52654, ECH-NE-14-00035 R0]
3.16 JF-03-00402, ARTS/MEOD Phase 1 Implementation 3.17 JAF-RPT-MISC-04489, Rev.7, Power-Flow Map Report 3.18 GE Hitachi, Effect of Cycle Extension on the Reload Stability Analyses for Options I-D, II and III, 0000-0125-2402-R0, November 2010 3.19 KGO-ENO-JB1-13-062, Applicability of GE Methods to Expanded Operating Domains, NEDC-33173P-A R4, November 2012.
3.20 KGO-ENO-EP1-14-113, SL MCPR Summary Results for FitzPatrick Cycle 22, Sept.15, 14.
3.21 GNF, 002N6416, R1, Raised Fuel Support Casting Fuel Impact Analysis for FitzPatrick Cycle 22, July 2015 [Accepted in EC5873 per EN-DC-149]
4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR):
The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.
4.2 Linear Heat Generation Rate (LHGR):
The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
4.3 Minimum critical power ratio (MCPR):
The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
4.4 Rated Recirculation Flow :
That drive flow which produces a core flow of 77.0 x 106 lb/hr.
Rev. No. 29 Page 5 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 5.0 RESPONSIBILITIES NOTE: See EN-LI-113 (Reference 3.1) 5.1 Shift Manager:
Assure that the reactor is operated within the limits described herein.
5.2 Reactor Engineering Supervisor:
Assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.4) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Evaluations of the licensing analyses documented in the SRLR-Rev.1 (Ref.3.8) were performed to address their applicability for plant operations with the elevated fuel support casting condition in Cycle 22 core location 38-39. The SRLR-Rev.1 evaluations for the four FSC affected bundles determined that if the four FSC affected bundles were specifically modeled to address the elevated fuel support casting, then a small increase in the OLMCPR for those four FSC affected bundles would be needed to ensure that the SLMCPR would be protected in the event of a limiting pressurization transient. The specific OLMCPR limits required per Reference 3.8 are documented in the COLR Table 8.1, Table 8.2, Table 8.3, or Table 8.4. The SRLR-Rev.1 analyses are applicable as long as the impacts of the elevated FSC on bundle flow and core bypass flow are addressed in the 3-D core performance calculations (3DM ).
Rev. No. 29 Page 6 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power > 25% of rated thermal power (RTP), the Operating Limit MCPR shall be equal to or greater than the limits given below.
7.1.1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR) 7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:
7.1.2.1 The average scram time to notch position 36 shall be:
AVE B n
N i i AVE = i =1 n
N i =1 i
7.1.2.2 The average scram time to notch position 36 is determined as follows:
WHERE:
n = Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i i = Average scram time to notch position 36 of all rods measured in surveillance test i.
Rev. No. 29 Page 7 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 7.1.2.3 The adjusted analysis mean scram time is calculated as follows:
1/2 N1 B ( sec ) = + 1.65 n Ni i=1 WHERE:
= Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.
= Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.
N1 = The total number of active rods measured in Technical Specification SR 3.1.4.4.
The number of rods to be scram tested and the test intervals are given in Technical Specification LCO 3.1.4, Control Rod Scram Times 7.1.3 When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table 8.1, Table 8.2, Table 8.3, or Table 8.4 as applicable for = 0.
7.1.4 WHEN the requirement 7.1.2.1 is not met (i.e. AVE > B), THEN the Operating Limit MCPR values (as a function of ) are given in Tables 8.1, 8.2, 8.3, or 8.4 as applicable.
AVE B A B WHERE:
AVE = The average scram time to notch position 36 as defined in 7.1.2.2.
B = The adjusted analysis mean scram time as defined in 7.1.2.3.
A = the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.
Rev. No. 29 Page 8 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.03 for conditions given in Tables 8.2, 8.3, or 8.4. No single-loop operation adder of 0.03 is needed for single-loop operation conditions specified in Table 8.1.
7.1.6 The Operating Limit MCPR is the greater of the flow and power dependent MCPR operating limits, MCPR(F) and MCPR(P).
Operating Limit MCPR = MAX (MCPR(P), MCPR(F))
The flow dependent MCPR operating limit, MCPR(F), is provided in Figure 8.1.
For core thermal powers equal to or greater than 25%, MCPR (P) is the product of the rated Operating Limit MCPR presented in Tables 8.1, 8.2, 8.3, or 8.4 and the K (P) factor presented in Figure 8.2.
7.2 Average Planar Linear Heat Generation Rate (APLHGR) 7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) 7.2.2 During operation, with thermal power > 25% rated thermal power (RTP),
the APLHGR shall be within the limits given in Table 8.5 for the appropriate fuel type.
7.2.3 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 above multiplied by the appropriate value (0.85 for GNF2 fuel, per Ref. 3.8).
Rev. No. 29 Page 9 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR) 7.3.2 During operation, with thermal power > 25% rated thermal power (RTP),
the applicable limiting LHGR values for each fuel rod as a function of axial location and exposure shall be the smaller of the power and flow dependent LHGR limits multiplied by the applicable power and flow adjustment or the LHGR limit multiplied by 0.85 (for GNF2) when in single loop operation.
LHGR limit = MIN (LHGR (P), LHGR (F)).
Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent LHGR limit adjustment factor, LHGRFAC (P), shown in Figure 8.4 and the LHGRstd in Table 8.6.
LHGR (P) = LHGRFAC(P) x LHGRstd The flow-dependent LHGR limit, LHGR (F), is the product of the LHGR flow dependent LHGR limit adjustment factor, LHGRFAC (F), shown in Figure 8.3 and the LHGRstd in Table 8.6.
LHGR (F) = LHGRFAC(F) x LHGRstd Rev. No. 29 Page 10 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 7.4 APRM Allowable Values (Digital Flow Cards) 7.4.1 APRM Flow Referenced Flux Scram Allowable Value (Run Mode) 7.4.1.1 Technical Specifications:
LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation 7.4.1.2 When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)
Allowable Value shall be for two loop operation:
S (% RTP) = 0.38*W+61.0% 0< W 24.7%
S (% RTP) = 1.15*W+42.0% 24.7< W 47.0%
S (% RTP) = 0.63*W+73.7% 47.0< W 68.7%
S (% RTP) = 117.00% (Clamp) W > 68.7%
for single loop operation:
S (% RTP) = 0.38*W+57.9% 0< W 32.7%
S (% RTP) = 1.15*W+32.8% 32.7< W 50.1%
S (% RTP) = 0.58*W+61.3% 50.1< W 95.9%
S (% RTP) = 117.00% (Clamp) W > 95.9%
WHERE:
S = Allowable value in percent of rated thermal power; W = Recirculation flow in percent of rated; 7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Allowable Value (Relocated to the Technical Requirements Manual)
Rev. No. 29 Page 11 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 7.5 RBM Upscale Rod Block Allowable Value 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block allowable value shall be:
S 0.66W + K for two loop operation; S 0.66W + K - 0.66 W for single loop operation; WHERE:
S = rod block allowable value in percent of initial; W = Loop flow in percent of rated K = Any intercept value may be used because the RBM intercept value does not affect the MCPR Operating Limit and the RBM is not assumed to function to protect the Safety Limit MCPR.
W = Difference between two loop and single loop effective drive flow at the same core flow.
NOTE: If K can be any value, then K - 0.66W can also be any value, and the allowable value adjustment for single loop operation is not necessary.
7.6 Stability Option 1-D Exclusion Region and Buffer Zone.
7.6.1 Technical Specification LCO 3.4.1, Recirculation Loops Operating 7.6.2 The reactor shall not be intentionally operated within the Exclusion Region given in Figure 8.5 when the SOLOMON Code is operable.
7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.5 when the SOLOMON Code is inoperable.
8.0 TABLES AND FIGURES 8.1 Following pages present Tables 8.1 through 8.6, and Figures 8.1 through 8.6. Exact tables and figures names are listed in the Table of Content on page 3.
Rev. No. 29 Page 12 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure GNF2 GNF2 fuel in Cell 38-39 BOC to MOC MOC to EOC BOC to MOC MOC to EOC
=0 1.43 1.49 1.47 1.53
>0.0 0.1 1.44 1.50 1.48 1.54
>0.1 0.2 1.45 1.51 1.49 1.55
>0.2 0.3 1.46 1.52 1.50 1.56
>0.3 0.4 1.47 1.53 1.51 1.57
>0.4 0.5 1.48 1.54 1.52 1.58
>0.5 0.6 1.49 1.55 1.53 1.59
>0.6 0.7 1.50 1.56 1.54 1.60
>0.7 0.8 1.51 1.57 1.55 1.61
>0.8 0.9 1.52 1.58 1.56 1.62
>0.9 1 1.53 1.59 1.57 1.63
Single Loop Operation ONLY----------------------------
GNF2 GNF2 fuel in Cell 38-39 BOC to MOC MOC to EOC BOC to MOC MOC to EOC
=0 1.48 1.52 1.50 1.56
>0.0 0.1 1.48 1.53 1.51 1.57
>0.1 0.2 1.48 1.54 1.52 1.58
>0.2 0.3 1.49 1.55 1.53 1.59
>0.3 0.4 1.50 1.56 1.54 1.60
>0.4 0.5 1.51 1.57 1.55 1.61
>0.5 0.6 1.52 1.58 1.56 1.62
>0.6 0.7 1.53 1.59 1.57 1.63
>0.7 0.8 1.54 1.6 1.58 1.64
>0.8 0.9 1.55 1.61 1.59 1.65
>0.9 1 1.56 1.62 1.60 1.66 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 29 Page 13 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE 8.2 MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service GNF2 GNF2 fuel in Cell 38-39 BOC to MOC MOC to EOC BOC to MOC MOC to EOC
=0 1.45 1.51 1.49 1.55
>0.0 0.1 1.46 1.52 1.50 1.56
>0.1 0.2 1.47 1.53 1.51 1.57
>0.2 0.3 1.48 1.54 1.52 1.58
>0.3 0.4 1.49 1.55 1.53 1.59
>0.4 0.5 1.50 1.56 1.54 1.60
>0.5 0.6 1.51 1.57 1.55 1.61
>0.6 0.7 1.52 1.58 1.56 1.62
>0.7 0.8 1.53 1.59 1.57 1.63
>0.8 0.9 1.54 1.60 1.58 1.64
>0.9 1 1.55 1.61 1.59 1.65 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 29 Page 14 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE 8.3 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service GNF2 fuel in GNF2 Cell 38-39 BOC to EOC BOC to EOC
=0 1.54 1.57
>0.0 0.1 1.55 1.58
>0.1 0.2 1.56 1.59
>0.2 0.3 1.57 1.60
>0.3 0.4 1.58 1.61
>0.4 0.5 1.59 1.62
>0.5 0.6 1.60 1.63
>0.6 0.7 1.61 1.64
>0.7 0.8 1.62 1.65
>0.8 0.9 1.63 1.66
>0.9 1 1.64 1.67 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Technical Specification LCO 3.7.6, Main Turbine Bypass System For single loop operation, these limits shall be increased as given in Section 7.1.5.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 29 Page 15 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE 8.4 MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction GNF2 fuel in GNF2 Cell 38-39 BOC to EOC BOC to EOC
=0 1.48 1.53
>0.0 0.1 1.49 1.54
>0.1 0.2 1.50 1.55
>0.2 0.3 1.51 1.56
>0.3 0.4 1.52 1.57
>0.4 0.5 1.53 1.58
>0.5 0.6 1.54 1.59
>0.6 0.7 1.55 1.60
>0.7 0.8 1.56 1.61
>0.8 0.9 1.57 1.62
>0.9 1 1.58 1.63 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.13) for further information. Not applicable for operation with Turbine Bypass Valves Out of Service.
Rev. No. 29 Page 16 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE 8.5 Exposure Dependent APLHGR Limits All GNF2 Fuel Types Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 13.78 13.24 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.85 for GNF2 fuel.
Linearly interpolate for APLHGR at intermediate exposure.
Rev. No. 29 Page 17 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 TABLE 8.6 Maximum LHGR Maximum LHGR - All GNF2 Fuel Types Peak Pellet Exposure, GWD/ST UO2 LHGR Limit, kW/ft
((` ` ` ` `````
````` `````
````` ````
````` ` ` ` ` ` ` ` ))
Peak Pellet Exposure, GWd/ST Most Limiting Gadolinia LHGR Limit, kW/ft
((` ` ` ` `````
````` `````
````` ````
```` ` ` ` ` ` ` ` ))
Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 22 core are provided in References 3.3, 3.14, and 3.15 LHGRstd values in the above Table 8.6 are subject to Power and Flow dependent adjustments per Section 7.3 For single loop operation these LHGR values shall be multiplied by 0.85 (for GNF2 fuel)
Linearly interpolate for LHGR at intermediate exposure Rev. No. 29 Page 18 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 Figure 8.1 MCPR(F) Factor C22 MCPR(f) 1.7 For Maximum Flow of 112%
Flow Dependent MCPR Factor - MCPR(F)
For SLO 1.6 Flow,% MCPR(F) 30.00 1.640 93.07 1.250 110 .0 1.250 1.5 For TLO Flow,% MCPR(F) 30.00 1.610 93.07 1.220 1.4 110.0 1.220 1.3 112%-SLO 1.2 112%-TLO 1.1 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Reference 3.8 Rev. No. 29 Page 19 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 Figure 8.2 K(P), OLMCPR(P) Factor 2.8 Operating Limit MCPR (P) = K(P)
- Operating Limit 2.7 MCPR(100)
Rated MCPR Multiplier - K(P) for P>29%, OLMCPR (P) for P<Pbypass 2.6 For P<25%: No Thermal Limits Monitoring Required, No limits specified 2.5 For 25%P<P(Bypass), P(Bypass)=29%
2.4 OLMCPR(P)=2.35+0.0129*(29%-P), Flow60%
OLMCPR(P)=2.63+0.0283*(29%-P), Flow>60%
2.3 For PP(Bypass)
K(P)=1.390+0.0118*(40%-P), 29%P<40%
2.2 K(P)=1.189+0.0101*(60%-P), 40%P<60%
K(P)=1.056+0.00532*(85%-P), 60%P<85%
2.1 K(P)=1.00+0.00373*(100%-P), 85%P<100%
2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1.0 20 30 40 50 60 70 80 90 100 110 Power (% rated)
See Table 8.1, 8.2, 8.3, and Table 8.4 for Operating Limit MCPR(100)
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Reference 3.8, 3.9 Rev. No. 29 Page 20 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 Figure 8.3 Flow-Dependent LHGR Multiplier, LHGRFAC(F) 1.10 1.00 APLHGR/LHGR Flow Factor - MAPFACf and LHGRFACf 0.90 0.80 0.70 0.60 LHGR(F)=LHGRFACf*LHGRstd Max Flow = 112%
Flow LHGRFACf 0.50 30% 0.626 85% 1.000 110% 1.000 0.40 0.30 30 40 50 60 70 80 90 100 110 Flow, % rated See Table 8.6 for LHGRSTD value Reference 3.8, 3.9 Rev. No. 29 Page 21 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 Figure 8.4 Power-Dependent LHGR Multiplier, LHGRFAC(P) 1.1 1.0 0.9 0.8 LHGRFAC(P)
0.7 LHGRFACp
For P<25%, No Thermal Limits Required Pbypass = 29% Pow er 0.6 for <29%P, >60%F LHGRFACp = 0.531+0.0045*(P-29) 0.5 for <29%P, 60%F LHGRFACp = 0.58 0.4 for 29%P100%
LHGRFACp = 1.000+0.00528*(P-100) 0.3 20 30 40 50 60 70 80 90 100 Power, % rated See Table 8.6 for LHGRSTD values Reference 3.8, 3.9 Rev. No. 29 Page 22 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 Figure 8.5 Stability Option 1-D Exclusion Region See References 3.17 and 3.8 for details Reference 3.18 generically removes cycle exposure limitation statement in the Supplemental Reload Licensing Report stability analysis.
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CORE OPERATING LIMITS REPORT CYCLE 22 Figure 8.6 Cycle 22 Loading Pattern by Bundle Design with the improperly seated FSC Cell 38-39 GNF2 Fuel Types marked North Reference 3.21 Rev. No. 29 Page 24 of 25
CORE OPERATING LIMITS REPORT CYCLE 22 9.0 USERS GUIDE The COLR defines thermal limits for the various operating conditions expected during the cycle. At the start of the cycle the 3D-Monicore databank limits are set for; Cycle exposure range of BOC to MOC
= 0 Dual recirculation pump operation Four steam line operation, and Normal Feedwater Temperature The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.
Procedure Change in Operating State Change in Limits Reference Cycle Exposure = EOR22- 3.483 GWD/ST See Table 8.1 for 0 for change in EN-DC-503 OLMCPR changes to EOC values at cycle MCPR. transition to exposure of 10.517 GWD/ST. Installed EOC limits databank will use SRLR R1 10.517 GWD/ST. will occur automatically Scram Time Test Results such that 0 Use new and see Table 8.1, 8.2, 8.3, Option B limits for OLMCPR must be and Table 8.4. RAP-7.4.1 interpolated with Option A limits Single Loop Operation The SLMCPR increases by 0.03 for OLMCPR, Switch to C22_OPTB_SLO_FSC.INP, therefore OLMCPR limits increase by 0.03, (or C22_OPTA_SLO_FSC.INP ). ST-40D except when 1.48 (Rated Equivalent SLO Afterwards, 3DM v6.59.06 will display Pump Seizure event is limiting for BOC- and use correct SLO OLMCPR.
MOC). Cell 38-39 GNF2 Fuel type OLMCPR limit arrays are added to core-wide GNF2 thermal limits.
Verify that 3D-Monicore has LHGR and MAPLHGR are reduced by a recognized the idle recirculation loop multiplier in SLO. and is applying the SLO GNF2 LHGR and MAPLHGR multipliers of 0.85.
Three Steam Line Operation (3SL) Increase OLMCPR according to Table None 8.2.
Operation with Turbine Bypass Valves Out- Increase OLMCPR according to Table None of-Service 8.3.
OLMCPR values increase, no LHGR change required Operation under Final Feedwater Temperature Increase OLMCPR according to Table None Reduction 8.4.
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